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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Fusion Science and Technology
Latest News
Taking shape: Fusion energy ecosystems built with public-private partnerships
It’s possible to describe fusion in simple terms: heat and squeeze small atoms to get abundant clean energy. But there’s nothing simple about getting fusion ready for the grid.
Private developers, national lab and university researchers, suppliers, and end users working toward that goal are developing a range of complex technologies to reach fusion temperatures and pressures, confounded by science and technology gaps linked to plasma behavior; materials, diagnostics, and electronics for extreme environments; fuel cycle sustainability; and economics.
Makoto Kobayashi, Akiko Hamada, Katsushi Matsuoka, Masato Suzuki, Junya Osuo, Yuki Edao, Satoshi Fukada, Toshihiko Yamanishi, Yasuhisa Oya, Kenji Okuno
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 56-60
Hydrogen/Tritium Behavior | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14112
Articles are hosted by Taylor and Francis Online.
Tritium release behavior for thermal neutron-irradiated Li0.17Pb0.83 eutectic alloy was studied. Main tritium release peak was observed in the temperature just a little higher than melting point in a thermal desorption spectrometry (TDS) experiment. Most of tritium release from Li0.17Pb0.83 eutectic alloy was found to be governed by diffusion process from the results of isothermal annealing experiments. Tritium diffusivity in a liquid state of Li0.17Pb0.83 eutectic alloy was evaluated to be D = 4.7 × 10-8 exp(-0.13 eV/kT) m2 s-1 . Tritium diffusivity was increased by the phase transition of Li0.17Pb0.83 eutectic alloy from a solid state to a liquid state, resulting in the sharp tritium release peak that appeared in TDS spectrum. In addition, about 4% of tritium was trapped in Li0.17Pb0.83 eutectic alloy as Li-T bond.